A description of the design of ITER as it has progressed during the first year of the Engineering Design Activities is given. The approach is guided by a conservative extrapolation of present-day tokamak physics and the intent to produce a device relevant to development of an attractive fusion reactor. The main parameters are determined by ensuring adequate confinement margin, and the beta -limit then permits a fusion power in excess of 3 GW. A major problem confronting the design is management of the exhaust of thermal power in the divertor. Progress on modeling plasma behavior in the novel divertor design proposed by Rebut is presented. A conceptual design of a first-wall and blanket using an advanced material (vanadium) and liquid lithium for cooling and breeding is also described.
Progress in the design of in-vessel components for ITER